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Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications
https://repo.qst.go.jp/records/48790
https://repo.qst.go.jp/records/48790b2c1950a-585f-40d2-a467-3646184db91c
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-04-23 | |||||
| タイトル | ||||||
| タイトル | Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications | |||||
| 言語 | ||||||
| 言語 | eng | |||||
| 資源タイプ | ||||||
| 資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
| 資源タイプ | journal article | |||||
| アクセス権 | ||||||
| アクセス権 | metadata only access | |||||
| アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
| 著者 |
Zinkle, S.J.
× Zinkle, S.J.× Boutard, J.L.× Hoelzer, D.T.× Kimura, A.× Lindau, R.× Odette, G.R.× Rieth, M.× Tan, L.× 谷川, 博康× 木村 晃彦× 谷川 博康 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Reduced activation ferritic/martensitic steels are currently the most technologically mature option for the structural material of proposed fusion energy reactors. Advanced next-generation higher performance steels offer the opportunity for improvements in fusion reactor operational lifetime and reliability, superior neutron radiation damage resistance, higher thermodynamic efficiency, and reduced construction costs. The two main strategies for developing improved steels for fusion energy applications are based on (1) an evolutionary pathway using computational thermodynamics modelling and modified thermomechanical treatments (TMT) to produce higher performance reduced activation ferritic/martensitic (RAFM) steels and (2) a higher risk, potentially higher payoff approach based on powder metallurgy techniques to produce very high strength oxide dispersion strengthened (ODS) steels capable of operation to very high temperatures and with potentially very high resistance to fusion neutron-induced property degradation. The current development status of these next-generation high performance steels is summarized, and research and development challenges for the successful development of these materials are outlined. Material properties including temperature-dependent uniaxial yield strengths, tensile elongations, high-temperature thermal creep, Charpy impact ductile to brittle transient temperature (DBTT) and fracture toughness behaviour, and neutron irradiation-induced low-temperature hardening and embrittlement and intermediate-temperature volumetric void swelling (including effects associated with fusion-relevant helium and hydrogen generation) are described for research heats of the new steels. | |||||
| 書誌情報 |
Nuclear Fusion 巻 57, 号 9, p. 092005, 発行日 2017-06 |
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| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1088/1741-4326/57/9/092005 | |||||
| 関連サイト | ||||||
| 識別子タイプ | URI | |||||
| 関連識別子 | http://iopscience.iop.org/article/10.1088/1741-4326/57/9/092005 | |||||
| 関連名称 | http://iopscience.iop.org/article/10.1088/1741-4326/57/9/092005 | |||||
